ML20033G900
| ML20033G900 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/31/1990 |
| From: | Newburgh G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| MP-90-353, NUDOCS 9004120365 | |
| Download: ML20033G900 (5) | |
Text
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i General Of fices e Seldea Street, Berlin. Connecticut UE[U"[IE[c7EINv' P.O. BOX 270
.u -a..tia assu m '
HARTF ORD. CONNECTICUT 06141-0270 J CC','02l;;3;;;
(20N 065 5000 L
L April 9, 1990 MP-90-353 Re:
10CTR50. 71 (a)
U.S. Nuclear Regulatory Commission Document Cont.01 Desk Washington, D.C.
20555
Reference:
Tacility Operating License DPR-21 Docket No. 50-245
Dear Sir:
In accordance with Millstone Unit 1 Technical Specification 6.9.1.6, the following monthly operating data report for Millstone Unit 1 is enclosed.
One additional copy of the report is enclosed.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY t -
06 Step en E. Scace Director, Millstone Station SES/GSN:cle Enclosurest (4) cc:
T. T. Martin, Regional Administrator Region I l
M. Boyle, NRC Project Manager, Millstone Unit No. 1 W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2 & 3 i
l l
$f j(
1
)
a AVERAGE DAILY UNIT POWER LEVEL DOOKET NO.
50-245 UNIT Millstone 1 DATE 900402 COMPLETE BY G. Newburch TELEPHONE (203) 447-1791 Extension 4400 MONTH March 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net),
(MWe-Net) 1 661 17 660 2
653-18 661 3
662 19 661 4
661 20 661 5
589 21 662 6
660 22 661 7
660 23 656 8
661 24 662 9
340 25 603 10 533 26 661 11 660 27 662 12 661 28 661 13 661 29 662 14 661 30 661 15 654 31 662 16 661 INSTRUCTIONS on this format, list the average daily unit power level in MWe-Net for each 1
day in the reporting month.
Computer to the nearest whole megawatt, i
L
t i
s i
OPERATING DATA REPORT DOCKET NO.
50-245 DATE 900402 COMPLETED BY G. Newburch TELEPHONE 1203) 447-1791 i
Extension 4400 l
i OPERATING STATUS 1.
Unit Name: Millstone 1 Notes:
2.
Reporting Period: March, 1990 l
3.
Licensed Thermal Power (MWt): 2011 1
4.
Nameplate Rating (Gross MWe): 662 5.
Design Electrical Rating (Net MWe): 660-6.
Maximum Dependable Capacity (Gross MWe):684 i
7.'
Maximum Dependable Capacity (Net MWe):654 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons:
N/A s
9.
Power Level to which Restricted, If Any (Net MWe):
N/A i
10.
Reasons For Restrictions, If Any:
N/A I
- 11. - Sours In Reporting Period 744 2,160 169,512
- 12. Number Of Hours Reactor Was Critical 744 2,160 134,524.9 13.
Reactor Reserve Shutdown Hours 0
0 3,283.3
~
14.
Hours Generator On-Line 744 2,160 131,236.8 15.
Unit Reserve Shutdown Hours 0
0 93.7 16.
Gross Thermal Energy Generated (MWH) 1.453,844
,4,271,211
~f45,668,748 17.
Gross Elec. Energy Cen0 rated (MWH) 498,900 1,466,600 82,888,696 18.
Net Electrical Energy Ginerated (MWH) 477,361 1,404,166 79,096,426 19.
Unit Service Factor 100 100 77.4 20.
Unit Availability Factor 100 100 77.5 21.
Unit Capacity Factor (Using MDC Net) 98.1 99.4 71.3 22.
Unit Capacity Factor (Using DER Net) 97.2 98.5 70.7 23.
Unit Forced Outage Rate 0
0 10.1 t
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
N/A 25.
If Shutdown at End of Report Period, Estimated Date of Startup:
N/A 26.
Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECIRICITY N/A N/A COMMERCIAL OPERATION N/A N/A
~
DOCKET NO. 50-245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 1 DATE 900402 COMPLETED BY G. Newburgh REPORT MONTH March, 1990 TELEPHONE (203) 447-1791 Extension 4400 No.
Date Type Duration Reason 2 Method of Licensee
. System Component Cause & Corrective l
(Hours)
Shutting Event Code
- Codes Action to Down Reactor 3 Report f Prevent Recurrence 90-02 900309 S
0 B
5 N/A N/A N/A Power reduction to find and repair condenser tube.
leaks and adjust control rod pattern 4
3 Method:
8 Exhibit G - Instructions 2 Reason:
1F: Forced S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test _
2-Manual Scram.
Entry Sheets for-Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)
E-Operator Training & License Examination previous month F-Administrative 5-Power Reduction sExhibit 1 - Same Source G-Operational Error (Explain)
(Duration = 0)
H-Other (Explain) 6-Other (Explain)
=
REFUELING INFORMATION LEQUEST 1.
Name of facility: Fd11 stone 1 2.
Scheduled date for next refueling shutdown: MARCH 1991 3.
Schedule date for restart following refueling: APRIL 1991 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes, Technicial Specification Changes Regarding:
(1) Maximum Average Planar Linear Heat Generating Rate (2) Maximum Critical Power katio 5.
Scheduled dateis) for submitting licensing action and supporting information:
Winter 1990-91 6.
Important licensing considerations' associated with refueling, e.g., new or different fuel desian or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
196 GEBB Fuel Assemblies 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a)
In Core:
(a) 580 (b) 1928 8.
The present licensed spent fuel pool storage capacity and the size of j
any increase in licensed storage capacity that has been requested or-is planned, in number of fuel assemblies:
Present capacity, 3229 assemblies 9.
The projected date of the last refueling that can-be discharged to the spent fuel pool assuming the present licensed capacity:
1997, Spent Fuel Pool, Full Core Off Load Capability is Reached i
a